ML101370307

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Proposed License Amendment Request Regarding Presure Boundary Designation for Pressurizer Power Operated Relief Valves
ML101370307
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/12/2010
From:
Plant Licensing Branch IV
To:
Gibson, Lauren, NRR/DORL/LPL4, 415-1056
Shared Package
ML101370300 List:
References
TAC ME3766
Download: ML101370307 (1)


Text

SUPPLEMENTAL INFORMATION NEEDED PROPOSED LICENSE AMENDMENT REQUEST REGARDING THE PRESSURE BOUNDARY DESIGNATION FOR THE PRESSURIZER POWER OPERATED RELIEF VALVES (PORVS)

AND THEIR ASSOCIATED BLOCK VALVES (ME3766)

WOLF CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-482 By letter dated April 13, 2010, (Agencywide Documents Access and Management System (ADAMS) Accession Number ML101100479), Wolf Creek Nuclear Operating Corporation (WCNOC) requested an amendment to the Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS). This license amendment request (LAR) is seeking approval by the Commission, pursuant to License Condition 2.C(5), to make changes to the approved fire protection program as described in the WCGS Updated Safety Analysis Report (USAR). Specifically, a revision to the response to Nuclear Regulatory Commission (NRC)

Question 280.5, documented on page 280-5 of the NRC Questions Section at the end of the USAR is requested regarding the removal of the high/low pressure interface designation from the pressurizer Power Operated Relief Valves (PORVs) and their associated block valves.

The above referenced license condition allows WCNOC to make changes to the approved fire protection program without prior NRC approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. WCNOC has determined that NRC review and approval of the proposed change is warranted.

The NRC Fire Protection Branch has reviewed the LAR and concluded that the scope of the analysis is incomplete (LIC-109, 3.1.2) since impacts on the plant are not discussed in the amendment. Therefore, additional information is needed to enable an independent assessment regarding the acceptability of the proposed amendment request.

To enable this independent assessment the following information is required:

  • Provide a description of the safety impact that the proposed license change would have on the plant.
  • Provide a description of any modifications or changes to the operation of the pressurizer Power Operated Relief Valves (PORVs) and their associated block valves, including electrical control circuits and cable rerouting, which would occur if this license change were accepted.
  • Provide a description of any changes to Post Fire Safe Shutdown Analysis, including new or revised procedures, operator manual actions and other operator post fire guidance documents, which would occur if this license change were accepted.